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Vacancy cluster growth and thermal recovery in hydrogen-irradiated tungsten

Journal of nuclear materials, 2020-04, Vol.531, p.152017, Article 152017

2020

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Quantitative AMS depth profiling of the hydrogen isotopes collected in graphite divertor and wall tiles of the tokamak ASDEX-Upgrade

Journal of nuclear materials, 1997-07, Vol.246 (1), p.9-16

1997

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Trapping of low-energy helium ions in niobium

Journal of nuclear materials, 1975-01, Vol.56 (3), p.365-367

1975

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The TEXTOR program at the KFA, Jülich

Journal of nuclear materials, 1976-01, Vol.63, p.96-99

Waelbroeck, F.

1976

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Influence of surface roughness on the sputter yield of Mo under keV D ion irradiation

Journal of nuclear materials, 2021-11, Vol.555, p.153135, Article 153135

2021

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Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade

Journal of nuclear materials, 2009-06, Vol.390, p.858-863

2009

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Deuterium retention in TiC and TaC doped tungsten at high temperatures

Journal of nuclear materials, 2015-08, Vol.463, p.1045-1048

2015

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Deuterium retention in tungsten damaged with W ions to various damage levels

Journal of nuclear materials, 2013-10, Vol.441 (1-3), p.280-285

2013

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An exploratory study on helium mobility in amorphous and crystallized bulk metallic glasses

Journal of nuclear materials, 2021-01, Vol.543, p.152617, Article 152617

2021

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Retention and enrichment of tungsten-containing carbon films under deuterium beam impact

Journal of nuclear materials, 2013-09, Vol.440 (1-3), p.257-271

2013

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Tungsten erosion at the ICRH limiters in ASDEX Upgrade

Journal of nuclear materials, 2007-06, Vol.363-365, p.112-116

2007

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Sputtering properties of tungsten ‘fuzzy’ surfaces

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S96-S99

2011

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EUROFER as wall material: Reduced sputtering yields due to W surface enrichment

Journal of nuclear materials, 2014-11, Vol.454 (1-3), p.1-6

2014

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Investigation of W components exposed to high thermal and high H/He fluxes

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.495-498

2011

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The erosion and retention properties of tungsten trioxide films exposed to low energy deuterium ions: Temperature dependence

Journal of nuclear materials, 2022-04, Vol.562, p.153590, Article 153590

2022

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Nanostructure formation on tungsten exposed to low-pressure rf helium plasmas: A study of ion energy threshold and early stage growth

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S104-S107

2011

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ELM mitigation techniques

Journal of nuclear materials, 2013-07, Vol.438, p.S11-S18

Evans, T.E.

2013

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Deuterium retention in self-damaged tungsten

Journal of nuclear materials, 2009-12, Vol.395 (1), p.150-155

2009

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The effect of displacement damage on deuterium retention in tungsten exposed to D neutrals and D2 gas

Journal of nuclear materials, 2013-07, Vol.438, p.S959-S962

2013

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Experimental studies and modeling of complete H-mode divertor detachment in ASDEX Upgrade

Journal of nuclear materials, 2015-08, Vol.463, p.128-134

2015

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Quantitative modeling of fuel retention in the JET-C and JET-ILW wall configurations by WallDYN and predictions for ITER

Journal of nuclear materials, 2015-08, Vol.463, p.66-72

2015

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Deuterium release from implanted beryllium and beryllium oxide

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S724-S727

2011

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EMC3-Eirene simulations of particle- and energy fluxes to main chamber- and divertor plasma facing components in ASDEX Upgrade compared to experiments

Journal of nuclear materials, 2015-08, Vol.463, p.744-747

2015

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Deuterium retention in Be:N:D codeposits

Journal of nuclear materials, 2013-07, Vol.438, p.S988-S991

2013

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Surface morphology and deuterium retention in tungsten oxide layers exposed to low-energy, high flux D plasma

Journal of nuclear materials, 2011-02, Vol.409 (1), p.27-32

2011

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Vacancy cluster growth and thermal recovery in hydrogen-irradiated tungsten

Quantitative AMS depth profiling of the hydrogen isotopes collected in graphite divertor and wall tiles of the tokamak ASDEX-Upgrade

Trapping of low-energy helium ions in niobium

The TEXTOR program at the KFA, Jülich

Influence of surface roughness on the sputter yield of Mo under keV D ion irradiation

Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade

Deuterium retention in TiC and TaC doped tungsten at high temperatures

Deuterium retention in tungsten damaged with W ions to various damage levels

An exploratory study on helium mobility in amorphous and crystallized bulk metallic glasses

Retention and enrichment of tungsten-containing carbon films under deuterium beam impact

Tungsten erosion at the ICRH limiters in ASDEX Upgrade

Sputtering properties of tungsten ‘fuzzy’ surfaces

EUROFER as wall material: Reduced sputtering yields due to W surface enrichment

Investigation of W components exposed to high thermal and high H/He fluxes

The erosion and retention properties of tungsten trioxide films exposed to low energy deuterium ions: Temperature dependence

Nanostructure formation on tungsten exposed to low-pressure rf helium plasmas: A study of ion energy threshold and early stage growth

ELM mitigation techniques

Deuterium retention in self-damaged tungsten

The effect of displacement damage on deuterium retention in tungsten exposed to D neutrals and D2 gas

Experimental studies and modeling of complete H-mode divertor detachment in ASDEX Upgrade

Quantitative modeling of fuel retention in the JET-C and JET-ILW wall configurations by WallDYN and predictions for ITER

Deuterium release from implanted beryllium and beryllium oxide

EMC3-Eirene simulations of particle- and energy fluxes to main chamber- and divertor plasma facing components in ASDEX Upgrade compared to experiments

Deuterium retention in Be:N:D codeposits

Surface morphology and deuterium retention in tungsten oxide layers exposed to low-energy, high flux D plasma

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